ML25150A016
| ML25150A016 | |
| Person / Time | |
|---|---|
| Site: | 99900003 |
| Issue date: | 06/06/2025 |
| From: | Glisan J NRC/NRR/DNRL/NLIB |
| To: | Karkour S GE Hitachi Nuclear Energy |
| Shared Package | |
| ML25150A015 | List: |
| References | |
| NEDO-34270, NEDC-34270P, EPID L-2025-TOP-0012 | |
| Download: ML25150A016 (1) | |
Text
From:
Jordan Glisan To:
Karkour, Suzanne (GE Vernova)
Cc:
Enfinger, Timothy (GE Vernova); bruce.bennett1@ge.com; bruce.bennett1@gevernova.us; Michelle Hayes; Mahmoud -MJ-Jardaneh; Rebecca Patton
Subject:
Acceptance Determination for NEDC-34270P/NEDO-34270, BWRX-300 Stability Analysis Topical Report Date:
Friday, June 6, 2025 4:09:00 PM Attachments:
image002.png NRC 898 - GEH BWRX-300 Stability Analysis LTR Completeness Determination.pdf Ms. Suzanne Karkour Vice President New Power Plant and Product Licensing GE Hitachi Nuclear Energy
Ms. Karkour,
Following receipt of the requested supplemental information (ML25141A240) needed to complete the acceptance review, the NRC staff accept the subject topical report for review.
Attached to this email youll find the completed form for the U.S. Nuclear Regulatory Commission staff topical report completeness determination for the submittal of GE-Hitachi BWRX-300 Stability Analysis. This form provides the completeness determination, key milestone dates, and an estimate of review hours. The review schedule assumes timely audit responses and a 30-day response to RAIs. The dates and resource estimates could change due to several factors, such as the timeframe for resolution of technical issues, Executive Order 12866 considerations, or other unanticipated factors.
Furthermore, acceptance of this topical report (TR) has been determined with the following caveats:
The BWRX-300 stability TR mentions the ((
)), while the analytical results presented use TGBLA06 and PANAC11. The staffs review will be limited to the use of the method with TGBLA06/PANAC11.
The BWRX-300 Stability TR includes a methodology for performing BWRX-300 stability analysis against Type II density wave oscillations but does not present the design basis calculations and all the relevant design information. The staffs review of the BWRX-300 Stability TR will focus on the methodology aspects, and a future applicant to construct or operate a BWRX-300 reactor would be expected to include the results of design basis calculations with supporting design information to provide the demonstration that limitation and condition 5.3 is met.
A future applicant to construct or operate a BWRX-300 reactor would need to demonstrate the general design criteria are met, and the staff would evaluate the compliance with those general design criteria at that time.
The BWRX-300 Stability TR requests approval that the only AOO that needs to be analyzed on a cycle-specific basis for stability is the loss of feedwater heating event.A decision on which events would be categorized as AOOs for the BWRX-300 design and the most limiting stability event would be reviewed and approved as part of a design review or licensing application to construct or operate a BWRX-300
reactor.As such, the staffs review and findings on this topical report methodology would be limited to confirming the thermal-hydraulic conditions and parameters that can reduce the stability margin during AOOs and the types of event progressions that may require cycle-specific analysis.The specific events requiring cycle-specific analysis or the most limiting stability event would be identified and reviewed as part of a design review or licensing application.
If you have any questions, please let me know.
Jordan Glisan Project Manager U.S. Nuclear Regulatory Commission NRR/DNRL/NLIB Phone: 301-415-3478